RBG-34088, Addendum to Semiannual Radioactive Effluent Release Rept for Jan-June 1990
| ML20058J979 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 06/30/1990 |
| From: | Cargill E, Fantacci C, Odell W GULF STATES UTILITIES CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RBG-34088, NUDOCS 9012060199 | |
| Download: ML20058J979 (8) | |
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GULF STATES UTILITIES COMPANY RIVER BIND ST ATION POST OFFICE Box 270 st IRANCISviti E tout $1ANA 7077%
ARE A CODE 604 615 60M 346 8661 l
l November 2 8,1990 t
RBG-34088 i
File Nos. G9.5, G9.25.1.5
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-l U. S. Nuclear Regulatory Cmmission Docunent Control Dask Washington, D. C.
20555 S
Gentiment River Bend Station - Unit l' l
Docket No. 50-458 I
Enclosed is the Mdendum to the Semiannual Radioactive Effluent Release Report for the period of January 1 to June 30, 1990 i
submitted to you ~ previously (ref.
RBG-33465 dated August 29, 1
1990).-
This-Mdendum provides infonnation which was not available at the time that the Semiannual Radioactive Effluent Release Report was being coupiled.
The Addendum is being subnitted in accordance with Technical Specification 6.9.1.8 of
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Appendix A to River Bend Station (RDS) License Number NPF-47.
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Sincerely, f
. H. Odell Manager-Oversight; q
River Bend Nuclear Group pg i
1 Enclosure cc:
U. S. Nuclear Regulatory Courdssion 611.Ryan Plaza Drive, Suite 1000
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Arlington, TX -76011-i- -
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NRC Resident Inspector q
Post Office Box 1051 St. Francisville, IA 70775 o:
9012060199 900630 r
PDR ADOCK 05000458 q
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RIVER BEND STATION - LNIT I SEMIANNUAL IUOIOACTIVE DTIUENT RELEASE REPORT NXWNDlM s,
REPORT PEIUOD: JANUARY 1,1990 TimOUGH JJtE 30, 1990 PREPARED BY:
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O /fM D'.
.'E'aritacci, Padiological Engiriedring Supervisor APPROVED BY:
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_E.8.Cargill,firector41adi 1 Programs
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SEMIANNUAL RADIONCTIVE EFFLUENT RELIASE REKMC ADDENDlN p
FACILITY:
River Bend Station - Unit I LICENSEE:
Gulf States Utilities Cmpany REPORT PERIOD:
January 1,1990 through June 30, 1990 This addendum is subnitted under River Bend Station (RBS) License-Number NPF-47. It provides infoITnation obtained frm vendor-perforned analysis of quarterly cmposite samples that was not available when the Quarter 1/2 1990 RBS Semiannual Radioactive Effluent Release Report was being empiled. Updates are provided for the following:
(1) Table 3 Gaseous Effluents - Sumation of all Releases Itms C.1 -
C.3, page 15 (2). Table 4 Gaseous: Effluents - Conditionally. Elevated Releases.
Itm 3, page 17 (3) Table 5 Gaseous Effluents - Ground Level Releases Item 3, page'20 (4) Table 6 _ Liquid Effluents - Sumnation of all Releases Itms A.1 -
A.3, page 23 (5) Table 6 Liquid Effluents - Sunmation of all Releases Item G, pages 251and 26 An entry of "0.00E+00" Ci in the following tables' indicates that the concentration of a particular radionuclide was below the Lower Limit of Detection (LLD).
GASEQUS EETLUENTS The Sr-90 caposite was below the minimum detectable activity (FDA) for the Fuel. Building and Radwaste Building exhaust vents.
'Ihe Sr-89 cmposite was below the minimum detectabic activity (FDA) for the Radwaste Building exhaust vent.
LIQUID EETTLMn'S The Sr-89 caposite was below the minimum detectable activity (FDA).
TMLE 3 ADDEMXM Effluent ard Waste Disposal Semi-Annual Report 1990 Year Gascous Effluents - Swmation of All Releases 1/2 Quarters
.______7_
gg l __ _
Unit louarter 1l Ouarter 2 l Error, %
l
.e C.
Particulates 1.
Particulates with half-
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'T lives of >9 dava-Ci PR 1.51E-04 1.86E+01
, 2.
Average release rate l
for period uCi/sec PR 1.92E-05 3.
Percent of technical
'F l
specification limit PR 7.22E-02 d.
4.
Gross alpha l
radioactivity l
Ci PR PR l
1
-PR - Previously Reported i i.
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1 a4-l TN LE 4 ADDENDEM i
EfDuent ard Waste Disposal Somiannual Ibport 1990 Year l
Gaseous Effluents - Corxlitionally Elevated Ibicases 1/2 Quarters l
l Continuous Mode Batch Mode i
_ j Nuclides Released Unit Quarter 1 l Quarter 2 I
Quarter 1 l Quarter 2 f
3.
Particulates i
l 7 -
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Strontium-89 Ci PR 1.37E-05 N/A N/A l
_ Ci PR 1.48E-05 N/A N/A
=-___7-q--.- _--- -.
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i Total for Period l
Ci l
PR l
1.50E-04 l
N/A l
N/A
'PR -.Previously Reported
7 TAIRE 5 NXRMXM Effluent ard Waste Disposal Samiannual Report 1990 Year Gaseous Effluents - Grourd IcVel Deleases 1/2 Quarters Continuous Mode ~
Batch Mode
.._____3______;
Nuclide' Released Unit Guarter 1 Ouarter 2 Quarter 1 Ouarter 2
?3.
Particulates I1I Strontium-89 Ci PR 7.26E-07 N/A N/A 7 Strontium-90~
Ci PR l
0.00E+00(2)
N/A N/A
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- 3. ___ -
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I 4
Total-for Period l
Ci PR 7.26E-07 l
N/A N/A' PR - Previously Reported
-(1). Quarterly ccuposite particulate filter analysis indicates a Minimum Detectable Activity (FDA) l concentration of <1.0E-16 uCi/cc for the Radwaste Building Exhaust Vent. This is less than the!
.Icuer.Idmit of Detection - (LID)- of 1.0E-11 uCi/ml as specified in table 4.11.2.1.2-1 of-RBS
. Technical' Specifications.
(2): _ Quarterly ccmposite particulate filter analysis indicates.a Mininum Detectable Activity- (FDA)!
concentration of <8.0 E-16 uCi/cc for the Fuel Bui' ding Exhaust Vent and <1E-16uC1/cc; for'.the!
Radwaste, Building Exhaust Vent. This is less Ean the Irwer Limit of Detection (LLD) of 1.01
- E-11 uCi/ml as sprified in table 4.11.2.1.2-1 of RBS Technical Specifications.
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l TAILE 6 ADDENGlM i
l Effluent and Wasto Diapnr.a1 Smi-Annual ikport 1990 Year i
Liquid Effluents - Sunnation of All Deleases 1]_2 Quarters
-l 2
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Unit Quarter 1l Ouarter 2 Error, %
A. - Fission and activation products 1.
Total relEa'se (niitiiET~~~~~'
T~~~~~ ~~'~l j
cluding, tritium, gases,j Ci PR j
1.52E-01 l 1.42E+01 l
l alpha l
2.
Average dilute ( concen-tration during period uC1/ml PR 1.01E-07
- 3. - Percent of applicable I
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limit ~
(1) l l
PR l
1,22E401
-l (1) One quarter of 3 Ci annual limit (1.25 C1) for liquid releases except for tritium or entrained noble gases frm 10CFR50 Appendix I.
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TABLE 6 ADDIH KM Effluent and Waste Disposal Saniannual Report 1990 Year I
G.
Liquid Effluent 1/2 Quarters Continuous Mode Batch Mode i
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Nuclides Released Unit Quarter 1
! Quarter 2 Quarter 1 Quarter 2 7.38E-04 ( 1 )
l Arsenic-76 Ci N/A N/A PR Strontitun Ci N/A N/A PR 0.00E+00 (2) l LStrontium-90 Ci N/A N/A PR 4.74E-04 Inon-55
'Ci N/A N/A PR 1.35E-03 L 'Ibtal For-Period Ci N/A l
N/A PR' l '1.85E+01 l
i i t-1 PR - Previously Reported a
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A (1). Arsenic-76 is resubnitte<' due to typographical error previously reported.
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'(2)- Analysis. of quarterly cciuposite - indicates a Mininun Detectable Activity a
(MDA) concentration of <5.0E-08 uCi/ml for Sr-89.
This value is less than f
the: IcWor Limit of Detection' (LLD) of 5.0 E-8 uCi/ml as specified in Table -
4.1111.1.1-1 of RBS Technical Specifications, j
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